Title :
The ARIES tokamak fusion reactor study
Author :
Najmabadi, Farrokh ; Conn, R.W. ; Bartlit, J.R. ; Bathke, C.G. ; Beecraft, W.R. ; Blanchard, J.P. ; Bromberg, L. ; Brooks, J. ; Cheng, E.T. ; Cohn, D.R. ; Cooke, P.I.H. ; Creedon, R.L. ; Ehst, D.A. ; Emmert, G.A. ; Evans, E.T., Jr. ; Ghoniem, N.M. ; Grotz
Author_Institution :
Dept. of Mech., Aerosp. & Nucl. Eng., California Univ., Los Angeles, CA, USA
Abstract :
The Advanced Reactor Innovation and Evaluation Study (ARIES) is a community effort to develop several visions of the tokamak as a fusion power reactor. The aims are to determine its potential economics, safety, and environmental features and to identify physics and technology areas with the highest leverage for achieving the best tokamak reactor. The authors focus on the ARIES-1 design. Parametric systems studies show that the optimum first stability tokamak has relatively low plasma current (~12 MA), high plasma aspect ratio (~4-6), and high magnetic field (~24 T at the coil). ARIES-I is a 1000-MWe (net) reactor with a plasma major radius of 6.5 m, a minor radius of 1.4 m, a neutron wall loading of about 2.8 MW/m2, and a mass power density of about 90 kWe/tonne. The ARIES-I reactor operates at steady state using ICRF (ion-cyclotron range of frequency) fast waves to drive current in the plasma core and lower-hybrid waves for edge-plasma current drive. The ARIES-I blanket is cooled by He and consists of SiC-composite structural material, Li4SiO4 solid breeder, and Be neutron multiplier, all chosen for their low-activation and low-decay after-heat in order to enhance the safety and environmental features of the design. The ARIES-I design has a competitive cost of electricity and superior safety and environmental features
Keywords :
Tokamak devices; fusion reactor materials; fusion reactor safety; fusion reactor theory and design; plasma heating; 1.4 m; 1000 MW; 24 T; 6.5 m; ARIES; ARIES tokamak; ARIES-1; Advanced Reactor Innovation and Evaluation Study; He cooling; ICRF; SiC-Li4SiO4-Be; blanket; edge-plasma current drive; lower-hybrid waves; magnetic field; major radius; mass power density; minor radius; neutron wall loading; plasma aspect ratio; safety; Fusion reactors; Inductors; Neutrons; Plasma density; Plasma stability; Power generation economics; Power system economics; Safety; Technological innovation; Tokamaks;
Conference_Titel :
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location :
Knoxville, TN
DOI :
10.1109/FUSION.1989.102387